Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels [electronic resource]
The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the code specify fatigue design curves for structural materials. While effects of reactor coolant environments are not explicitl...
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Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. :
distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1998.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels |h [electronic resource] |
| 260 | |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1998. | ||
| 300 | |a 125 p. | ||
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| 500 | |a "NUREG/CR--6583" | ||
| 500 | |a "ANL--97/18" | ||
| 500 | |a "TI98002917" | ||
| 500 | |a Chopra, O.K.; Shack, W.J. | ||
| 500 | |a Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology. | ||
| 500 | |a Nuclear Regulatory Commission, Washington, DC (United States) | ||
| 520 | 3 | |a The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the code specify fatigue design curves for structural materials. While effects of reactor coolant environments are not explicitly addressed by the design curves, test data indicate that the Code fatigue curves may not always be adequate in coolant environments. This report summarizes work performed by Argonne National Laboratory on fatigue of carbon and low-alloy steels in light water reactor (LWR) environments. The existing fatigue S-N data have been evaluated to establish the effects of various material and loading variables such as steel type, dissolved oxygen level, strain range, strain rate, temperature, orientation, and sulfur content on the fatigue life of these steels. Statistical models have been developed for estimating the fatigue S-N curves as a function of material, loading, and environmental variables. The results have been used to estimate the probability of fatigue cracking of reactor components. The different methods for incorporating the effects of LWR coolant environments on the ASME Code fatigue design curves are presented. | |
| 536 | |b W-31109-ENG-38. | ||
| 650 | 7 | |a Carbon Steels. |2 local. | |
| 650 | 7 | |a Low Alloy Steels. |2 local. | |
| 650 | 7 | |a Fatigue. |2 local. | |
| 650 | 7 | |a Bwr Type Reactors. |2 local. | |
| 650 | 7 | |a Pwr Type Reactors. |2 local. | |
| 650 | 7 | |a Reactor Materials. |2 local. | |
| 650 | 7 | |a Coolants. |2 local. | |
| 650 | 7 | |a Crack Propagation. |2 local. | |
| 650 | 7 | |a Water Chemistry. |2 local. | |
| 650 | 7 | |a Corrosive Effects. |2 local. | |
| 650 | 7 | |a Corrosion Fatigue. |2 local. | |
| 650 | 7 | |a Experimental Data. |2 local. | |
| 650 | 7 | |a Materials Science ;21 Nuclear Power Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Argonne National Laboratory. |4 res. | |
| 710 | 2 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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